NDLI: R&D Towards HTS Current Leads for ITER

Content Provider	IEEE Xplore Digital Library
Author	Bauer, P. Yanfang Bi Anyi Cheng Devred, A. Kaisong Ding Xiongyi Huang Kun Lu Mitchell, N. Sahu, A.K. Guang Shen Yuntao Song Tingzhi Zhou
Copyright Year	2002
Abstract	The ITER Organization (IO) and the Institute of Plasma Physics at the Chinese Academy of Sciences (ASIPP) are jointly developing the 68 kA current leads using High Temperature Superconductors for the superconducting Toroidal Field (TF) magnet system of the International Thermonuclear Experimental Reactor, ITER. The proposed design consists of a conventional helium cooled heat exchanger operating between 65 K and 320 K and an HTS module covering the low temperature end using Bi-2223 tapes. The first HTS current lead prototypes will be tested in the EAST tokamak facility at ASIPP. This paper discusses the design of the first, 68 kA, TF HTS lead, which is the main emphasis of this first stage of the ITER current lead development program.
Sponsorship	Council on Superconductivity Appl. Superconductivity Conference Inc MIT
Starting Page	1500
Ending Page	1503
Page Count	4
File Size	412382
File Format	PDF
ISSN	10518223
Volume Number	19
Issue Number	3
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	2009-06-01
Publisher Place	U.S.A.
Access Restriction	One Nation One Subscription (ONOS)
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	High temperature superconductors Plasma temperature Superconducting magnets Nuclear and plasma sciences Physics Superconducting films Toroidal magnetic fields Inductors Prototypes superconducting magnets Bi2223 fusion tokamak HTS current leads
Content Type	Text
Resource Type	Article
Subject	Condensed Matter Physics Electronic, Optical and Magnetic Materials Electrical and Electronic Engineering

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Safety Research of the 68 kA Trial-HTS Current Lead for ITER

Test Results of 52/68 kA Trial HTS Current Leads for ITER

Assurance of Sound Manufacturing Technology for the ITER Current Leads

Safety Analysis of the 70 kA ITER HTS Current Lead Demonstrator

Design of the HTS Current Leads for ITER

Test of a 10 kA HTS Current Lead for ITER

High Temperature Superconductor Current Leads for WENDELSTEIN 7-X and JT-60SA

Design of the ITER TF Magnet Feeder Systems

Development of Persistent-Current Mode HTS Coil for the RT-1 Plasma Device

R&D Towards HTS Current Leads for ITER

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